CN117214045A - Method for researching radioactive aerosol release behavior in metal waste cutting process - Google Patents
Method for researching radioactive aerosol release behavior in metal waste cutting process Download PDFInfo
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- CN117214045A CN117214045A CN202311028598.0A CN202311028598A CN117214045A CN 117214045 A CN117214045 A CN 117214045A CN 202311028598 A CN202311028598 A CN 202311028598A CN 117214045 A CN117214045 A CN 117214045A
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- 239000010814 metallic waste Substances 0.000 title claims abstract description 124
- 238000005520 cutting process Methods 0.000 title claims abstract description 111
- 239000000443 aerosol Substances 0.000 title claims abstract description 64
- 238000000034 method Methods 0.000 title claims abstract description 47
- 230000002285 radioactive effect Effects 0.000 title claims abstract description 47
- 229910052751 metal Inorganic materials 0.000 claims abstract description 31
- 239000002184 metal Substances 0.000 claims abstract description 31
- 229910052770 Uranium Inorganic materials 0.000 claims abstract description 29
- JFALSRSLKYAFGM-UHFFFAOYSA-N uranium(0) Chemical compound [U] JFALSRSLKYAFGM-UHFFFAOYSA-N 0.000 claims abstract description 29
- 239000002699 waste material Substances 0.000 claims abstract description 26
- 230000000694 effects Effects 0.000 claims description 26
- 238000005070 sampling Methods 0.000 claims description 21
- 230000008569 process Effects 0.000 claims description 18
- 238000012544 monitoring process Methods 0.000 claims description 16
- 239000002245 particle Substances 0.000 claims description 11
- 238000011109 contamination Methods 0.000 claims description 8
- 239000007789 gas Substances 0.000 claims description 7
- 238000009423 ventilation Methods 0.000 claims description 4
- 239000012528 membrane Substances 0.000 claims description 3
- 238000011160 research Methods 0.000 abstract description 6
- 239000002901 radioactive waste Substances 0.000 abstract description 5
- 150000002739 metals Chemical class 0.000 abstract description 4
- 238000002360 preparation method Methods 0.000 abstract description 3
- 230000007613 environmental effect Effects 0.000 abstract description 2
- 230000005855 radiation Effects 0.000 abstract description 2
- 239000000463 material Substances 0.000 description 14
- 238000003860 storage Methods 0.000 description 5
- XEEYBQQBJWHFJM-UHFFFAOYSA-N Iron Chemical compound [Fe] XEEYBQQBJWHFJM-UHFFFAOYSA-N 0.000 description 4
- 229910000975 Carbon steel Inorganic materials 0.000 description 3
- 238000003723 Smelting Methods 0.000 description 3
- 239000010962 carbon steel Substances 0.000 description 3
- 239000000428 dust Substances 0.000 description 3
- 238000011835 investigation Methods 0.000 description 3
- 238000004064 recycling Methods 0.000 description 3
- 239000010935 stainless steel Substances 0.000 description 3
- 229910001220 stainless steel Inorganic materials 0.000 description 3
- 230000003750 conditioning effect Effects 0.000 description 2
- 238000011038 discontinuous diafiltration by volume reduction Methods 0.000 description 2
- 229910052742 iron Inorganic materials 0.000 description 2
- 238000012986 modification Methods 0.000 description 2
- 230000004048 modification Effects 0.000 description 2
- 229910000897 Babbitt (metal) Inorganic materials 0.000 description 1
- 229910000831 Steel Inorganic materials 0.000 description 1
- 230000004075 alteration Effects 0.000 description 1
- 238000004458 analytical method Methods 0.000 description 1
- 230000009286 beneficial effect Effects 0.000 description 1
- WUKWITHWXAAZEY-UHFFFAOYSA-L calcium difluoride Chemical group [F-].[F-].[Ca+2] WUKWITHWXAAZEY-UHFFFAOYSA-L 0.000 description 1
- 238000004364 calculation method Methods 0.000 description 1
- 239000004568 cement Substances 0.000 description 1
- 239000010849 combustible waste Substances 0.000 description 1
- 238000005202 decontamination Methods 0.000 description 1
- 230000003588 decontaminative effect Effects 0.000 description 1
- 238000001514 detection method Methods 0.000 description 1
- 230000009977 dual effect Effects 0.000 description 1
- 238000002474 experimental method Methods 0.000 description 1
- 238000001914 filtration Methods 0.000 description 1
- 239000007788 liquid Substances 0.000 description 1
- 238000004519 manufacturing process Methods 0.000 description 1
- 239000003758 nuclear fuel Substances 0.000 description 1
- 238000011084 recovery Methods 0.000 description 1
- 239000003923 scrap metal Substances 0.000 description 1
- 238000012216 screening Methods 0.000 description 1
- 238000010008 shearing Methods 0.000 description 1
- 239000002689 soil Substances 0.000 description 1
- 239000002910 solid waste Substances 0.000 description 1
- 239000010959 steel Substances 0.000 description 1
Classifications
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- Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
- Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
- Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
- Y02E30/00—Energy generation of nuclear origin
- Y02E30/30—Nuclear fission reactors
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- Measurement Of Radiation (AREA)
Abstract
The invention discloses a research method of radioactive aerosol release behavior in a metal waste cutting process, which combines the pollution level of radioactive metal waste, related parameters before and after uranium-containing metal waste cutting and the radioactive aerosol release share estimation relationship in the cutting process, establishes a release source item estimation method, and obtains the aerosol release shares of waste metals with typical cutting modes and different pollution levels in the cutting process. The method can be used for calculating the aerosol release share of the radioactive waste cutting process, and provides powerful data support for radiation protection and environmental protection in the preparation process.
Description
Technical Field
The invention belongs to the technical field of radioactive waste disposal, and particularly relates to a research method of radioactive aerosol release behavior in a metal waste cutting process.
Background
At present, along with the operation and retirement of various nuclear facilities, a large amount of radioactive waste is generated, and the whole nuclear facility has the characteristics of large waste amount, multiple waste types and multiple temporary storage. According to current nuclear facility operation practice, the generated solid waste types comprise metal waste, combustible waste, incombustible waste and the like, the incombustible waste such as filter cores, polluted soil, calcium fluoride residues and waste radioactive sources are classified and then sent to a very low-level and low-level disposal site for disposal according to radioactivity level, other types of waste are subjected to waste volume reduction and minimization by adopting other disposal modes, for example, smelting and recycling of the metal waste, overpressure treatment is carried out on compressible waste, and compressed cakes are filled into a small steel box for cement fixation to meet the receiving standard of the disposal site. The volume reduction, decontamination and recycling of the wastes are realized by the treatment method, the storage and disposal sites of the radioactive wastes are reduced, the recycling of the wastes is realized, the minimization requirement of the radioactive wastes is met, and the social and economic dual benefits can be obtained.
During the production and retirement of nuclear fuel cycle front-end facilities, a large amount of uranium-containing waste metal can be generated, and the waste can be recycled through a metal smelting method. Before transferring and smelting, the uranium-containing waste metal needs to be cut into large pieces of equipment to meet shipment requirements, wherein the large pieces of equipment comprise cutting modes such as cold cutting, gas cutting and plasma cutting, the large pieces of waste metal comprise ventilation pipelines, liquid conveying pipelines, large storage tanks or containers, glove boxes and the like, the surface pollution levels of the large pieces of waste metal are different, and radioactive aerosols with different degrees can be generated in the cutting process for the waste metals with different cutting modes and different pollution levels.
However, no related research method for radioactive aerosol release share in the scrap metal cutting process is reported in the prior art.
Disclosure of Invention
The invention aims to provide a research method for radioactive aerosol release share in the radioactive metal waste cutting process.
In order to achieve the above purpose, the invention adopts the following technical scheme: a method for studying the release behavior of radioactive aerosols during the cutting of metal wastes, comprising the steps of:
(1) Determining pollution source items of radioactive metal waste, and calculating the total activity of the metal waste;
(2) Cutting the metal waste, and monitoring a cutting parameter and a radioactive aerosol parameter released in the cutting process;
(3) Calculating the release share of radioactive aerosol in the cutting process;
(4) The radioaerosol inhalable fraction of the cutting process was calculated.
Further, in the step (1), pollution source item investigation of radioactive metal waste is performed, wherein the pollution source item investigation comprises batch of the metal waste and total activity monitoring of various uranium-containing metal waste.
Further, the batch of the metal waste comprises the type, the material and the thickness of the metal waste, the type of the metal waste mainly comprises a process pipeline, an exhaust pipe, a storage tank, a container, waste equipment, a valve and the like, and the material of the metal waste mainly comprises carbon steel, stainless steel, iron and the like; uranium-containing metal wastes of the same type and material and substantially uniform thickness are divided into batches.
Further, the total activity monitoring of the various metal wastes comprises the total activity monitoring of waste metal, a process pipeline and an exhaust pipe.
Further, the total activity of the metal waste is calculated by a formula (1) of a surface pollution level value K and a metal density rho;
D＝K×M/(ρ×h) (1)
wherein d—activity of a batch of metal waste; k—surface contamination level of certain batches of metal waste; ρ—density of certain batch of metal waste; h- -thickness of a batch of metal waste.
Further, the total activity of the process pipeline and the exhaust pipe is calculated by a formula (2);
D＝K 1 ×M/2(ρ×h)+K 2 ×M/2(ρ×h) (2)
wherein D- -activity of uranium-containing metal waste of pipeline type; k (K) 1 -the level of contamination of the outer surface of the uranium-containing metal waste of the pipeline type; k (K) 2 -the level of contamination of the inner surface of the uranium-containing metal waste of the pipeline type; ρ—density of uranium-containing metal waste of pipeline type; h- -thickness of the uranium-containing metal waste of the pipeline type.
Further, in the step (2), cutting mode, cutting rate, cutting temperature and cutting time data in the process parameters of metal waste gas cutting, plasma cutting and metal cutting are monitored.
In the step (2), metal waste is cut in an air curtain, an aerosol sampling device and a particle size divider are arranged at an air outlet under the condition of certain technological parameters, the sampling amount of the aerosol is determined according to the single cutting amount, the operation duration and the ventilation times of the air curtain, the sampling volume and the sampling time are recorded, and the concentration of the aerosol nuclide in the metal waste cutting process is obtained through analysis of a sampling filter membrane.
Further, in the step (3), the aerosol release fraction of the metal waste cutting process is calculated by the formula (3),
ARF＝Q×C i ×T/(D×t) (3)
wherein ARF- -the aerosol release fraction of the metal waste cutting and conditioning process, D- -the total activity of a batch of metal waste, Q- -the aerosol sample size, C i Aerosol nuclide concentration, T-cut time, T-sample time.
Further, in the step (4), the particle size of the particles is counted according to the sampling monitoring result of the particle size divider<Aerosol concentration of PM10 (C i-10 ) An inhalable fraction (RF) is obtained.
The invention also provides application of the research method for the release behavior of the radioactive aerosol in the metal waste cutting process, which is used for calculating the release share of the radioactive aerosol in the uranium-containing metal waste cutting process.
The technical scheme of the invention has the beneficial effects that the method for researching the radioactive aerosol release behavior in the metal waste cutting process combines the pollution level of the radioactive metal waste, the pollution source items before cutting, aerosol monitoring data in the cutting process, the cutting area and the cutting quantity, establishes a release source item estimation method according to the radioactive aerosol release share estimation relation of each parameter in the metal waste cutting process, and acquires the aerosol release shares of waste metals with different pollution levels in the typical cutting mode. The method can be effectively applied to calculation of the radioactive aerosol release share of the radioactive metal waste to be cut in the preparation process, and provides powerful data support for radiation protection and environmental protection in the preparation process.
Drawings
FIG. 1 is a flow chart of a method according to an embodiment of the present invention.
Detailed Description
The present invention will be described in detail with reference to the accompanying drawings and examples.
Referring to fig. 1, an embodiment of the present invention provides a method for researching a radioactive aerosol release behavior in a metal waste cutting process, including the following steps:
(1) Determining pollution source items of radioactive metal waste, and calculating the total activity of the metal waste;
(2) Cutting the metal waste, and monitoring a cutting parameter and a radioactive aerosol parameter released in the cutting process;
(3) Calculating the release share of radioactive aerosol in the cutting process;
(4) The radioaerosol inhalable fraction of the cutting process was calculated.
Preferably, in the step (1), the pollution source item investigation of the radioactive metal waste comprises batch-wise monitoring of the total activity of the uranium-containing metal waste.
Preferably, the batch of the uranium-containing metal waste comprises the type, the material and the thickness of the metal waste, the type of the uranium-containing metal waste mainly comprises a process pipeline, an exhaust pipe, a storage tank, a container, a waste device, a valve and the like, and the material of the uranium-containing metal waste mainly comprises carbon steel, stainless steel, iron and the like; uranium-containing metal wastes of the same type and material and substantially uniform thickness are divided into batches.
Preferably, the monitoring of the total activity of the uranium-containing metal wastes comprises monitoring of the total activity of waste metals, process pipelines and exhaust pipes.
The source survey of uranium-containing metal waste includes an inner surface and an outer surface of metal, with the inner surface typically having a higher concentration of radioactivity than the outer surface for the metal waste. And when the source item is investigated, selecting metal wastes of different types (such as different types of pipelines, metal brackets and the like), thicknesses and materials in batches, respectively selecting representative metal equipment, measuring the surface pollution level of the metal equipment, and multiplying the surface pollution data of the unit area by the surface area of the metal piece to obtain the radioactivity of the surface pollution of the metal wastes.
Preferably, the total activity of the waste metal is calculated by a formula (1) of a surface pollution level value K and a metal density rho of uranium-containing metal waste;
D＝K×M/(ρ×h) (1)
wherein d—activity of a batch of metal waste; k—surface contamination level value for a batch of metal waste; m- -the weight of the material before and after cutting; ρ—density of certain batch of metal waste; h- -thickness of a batch of metal waste.
The surface pollution K of each batch of metal waste is measured by adopting a surface pollution measuring instrument, the type of the polluted nuclide and the material information of the metal waste are analyzed according to the source of the waste metal, the material weight and the metal type (carbon steel, stainless steel and the like) are included, the material information is recorded, and the material weight M and the material thickness h before and after the material cutting are measured.
Preferably, the total activity of the process pipeline and the exhaust pipe is calculated by a formula (2);
D＝K 1 ×M/2(ρ×h)+K 2 ×M/2(ρ×h) (2)
wherein D- -activity of the pipeline metal waste; k (K) 1 -the external surface pollution level value of the pipeline metallic waste; k (K) 2 -the level of pollution of the inner surface of the metallic waste of the pipeline; ρ—density of pipeline metal like waste; h- -thickness of the pipeline metal waste.
For metal waste such as process piping, exhaust pipes, etc., there are cases where the inner surfaces of the piping are contaminated, and the estimation of the radioactive source term is performed assuming that the contamination levels of the inner and outer surfaces respectively occupy half the mass of the same type of metal waste in the area.
The method for measuring the metal waste in the same batch adopts random sampling detection, the sampling quantity is determined according to the total quantity of the metal waste in the batch, the monitoring times are 8-20 times, the average value of the surface pollution monitoring results is taken as the surface pollution level value K of the metal waste in the batch, and the total activity of the metal waste in the batch is calculated by combining the formula (1) or the formula (2).
Preferably, in the step (2), cutting mode, cutting rate, cutting temperature and cutting time data in the process parameters of metal waste gas cutting, plasma cutting and metal cutting are monitored.
The cutting of the metal waste adopts various cutting methods, and the cutting of the uranium-containing metal waste in the embodiment of the invention comprises plasma cutting, gas cutting, metal shearing and the like. Send uranium-bearing metal waste to fixed mesa and cut, the cutting platform sets up the wind gap, and the aerosol that produces when cutting passes through the hose and links to each other with metal cutting dust remover, sets up the removal dust remover simultaneously, is also connecting metal cutting dust remover, collects filtration to the tail gas, and operating personnel should set up mouth nose protection baffle when cutting, reduces the influence of radioactive aerosol to operating personnel. The resulting aerosol is filtered and discharged to the environment. The metal waste after cutting decontaminates, is temporarily stored after being packed by a packer, and is uniformly sent to a recovery unit for disposal.
Preferably, in the step (2), metal waste is cut in an air curtain, an aerosol sampling device and a particle size divider are arranged at an air outlet under the condition of certain technological parameters, the sampling amount of the aerosol is determined according to the single cutting amount, the operation duration and the ventilation times of the air curtain, the sampling volume and the sampling time are recorded, and the concentration of the aerosol nuclide in the metal waste cutting process is obtained by analyzing a sampling filter membrane.
The embodiment of the invention performs metal cutting operation in the air curtain, and the technological parameters of gas cutting, plasma cutting and metal cutting are collected when uranium-containing metal waste is cut, and mainly comprise a cutting mode, a cutting rate, a cutting temperature, a cutting time and the like. Screening typical process parameters, carrying out key parameter setting, and recording the process parameters to obtain the optimal process parameters for cutting the radioactive metal waste.
Preferably, in the step (3), the aerosol release fraction of the uranium-containing metal waste cutting process is calculated by formula (3),
ARF＝Q×C i ×T/(D×t) (3)
wherein ARF- -the aerosol release fraction of the metal waste cutting and conditioning process, D- -the total activity of a batch of metal waste, Q- -the aerosol sample size, C i Aerosol nuclide concentration, T-cut time, T-sample time.
Preferably, the metal waste cutting experiment of the same batch is carried out 3 to 5 times, multiple ARF values are obtained, and an average value is calculated.
Preferably, in the step (4), the particle size is counted by sampling the monitoring result of the particle size divider<PM 10 Aerosol concentration (C) i-10 ) Obtaining an inhalable fraction (RF), rf=c i-10 /C i 。
The embodiment of the invention also provides application of the research method of the radioactive aerosol release share in the metal waste cutting process, which is used for calculating the release share of the radioactive aerosol in the uranium-containing metal waste cutting process.
It will be apparent to those skilled in the art that various modifications and variations can be made to the present invention without departing from the spirit or scope of the invention. Thus, it is intended that the present invention also include such modifications and alterations insofar as they come within the scope of the appended claims or the equivalents thereof.
Claims (9)
1. A method for researching radioactive aerosol release behavior in a metal waste cutting process, which is characterized by comprising the following steps:
(1) Determining pollution source items of radioactive metal waste, and calculating the total activity of the metal waste;
(2) Cutting the metal waste, and monitoring a cutting parameter and a radioactive aerosol parameter released in the cutting process;
(3) Calculating the release share of radioactive aerosol in the cutting process;
(4) The radioaerosol inhalable fraction of the cutting process was calculated.
2. The method for studying the release behavior of radioactive aerosols during the cutting of metal wastes according to claim 1, wherein in the step (1), the pollution source item of the radioactive metal wastes is investigated, comprising monitoring the total activity of the batch of uranium-containing metal wastes and the various types of uranium-containing metal wastes.
3. The method for studying the release behavior of radioactive aerosols during the cutting of metal wastes according to claim 1, wherein in the step (1), the total activity of the metal wastes is calculated by the formula (1) of the surface contamination level value K and the metal density ρ;
D＝K×M/(ρ×h) (1)
wherein d—activity of a batch of metal waste; k—surface contamination level of certain batches of metal waste; ρ—density of certain batch of metal waste; h- -thickness of a batch of metal waste.
4. The method for studying the release behavior of radioactive aerosols in the process of cutting metal wastes according to claim 1, wherein in the step (1), the total activity of the process pipe and the exhaust pipe in the metal wastes is calculated by the formula (2);
D＝K 1 ×M/2(ρ×h)+K 2 ×M/2(ρ×h) (2)
wherein D- -activity of the pipeline metal waste; k (K) 1 -the level of pollution of the outer surface of the metallic waste of the pipeline; k (K) 2 -the level of contamination of the inner surface of the pipeline metallic waste; ρ—density of pipeline metal like waste; h- -thickness of the pipeline metal waste.
5. The method for studying the release behavior of radioactive aerosols in metal waste cutting process of claim 1, wherein in the step (2), cutting mode, cutting rate, cutting temperature and cutting time data in the process parameters of metal waste gas cutting, plasma cutting and metal cutting are monitored.
6. The method for researching the release behavior of radioactive aerosol in the metal waste cutting process according to claim 1, wherein in the step (2), metal waste is cut in an air curtain, an aerosol sampling device and a particle size divider are arranged at an air outlet under the condition of a certain technological parameter, the sampling amount of the aerosol is determined according to the single cutting amount, the operation duration and the air curtain ventilation times, the sampling volume and the sampling time are recorded, and the concentration of the nuclide of the aerosol in the metal waste cutting process is obtained by analyzing a sampling filter membrane.
7. A method for studying the release behavior of radioactive aerosols during the cutting of metal wastes according to claim 1, wherein in said step (3), the aerosol release fraction during the cutting of metal wastes is calculated by the formula (3),
ARF＝Q×C i ×T/(D×t) (3)
wherein, ARF- -the release share of aerosol in the uranium-containing metal waste cutting and preparing process, D- -the total activity of certain batch of uranium-containing metal waste, Q- -the sampling amount of aerosol, C i Aerosol nuclide concentration, T-cut time, T-sample time.
8. The method for studying the release behavior of radioactive aerosols in a metal waste cutting process of claim 6 wherein in step (4), the particle size of the particles is counted based on the result of the sampling monitoring by the particle size divider<PM 10 Aerosol concentration (C) i-10 ) An inhalable fraction (RF) is obtained.
9. Use of a method for studying the release behaviour of radioactive aerosols during the cutting of metallic wastes according to any one of claims 1 to 8, for calculating the release fraction of radioactive aerosols during the cutting of uranium-containing metallic wastes.
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